Manufacturing of the Wendelstein 7-X divertor and wall protection

Benhard, S.; Streibl, B.; Boscary, J.; Greuner, H.; Grigull, P.; Kißlinger, J.; Li, C.; Mendelevitch, B.; Pirsch, T.; Rust, N.; Schweizer, Sabine; Vorköper, A.; Weissgerber, M.

doi:10.1016/j.fusengdes.2005.06.102

Cited by 12 publications

(5 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Plasma confinement devices of the present day are equipped with a sufficiently thick and solid first wall to protect the vacuum vessel from the incident heat and particles originating from scrape-off-layer plasma and charge exchange particles [8][9][10][11]. In the fusion reactor, a blanket, whose function will also be to breed tritium fuel, must be installed facing the plasma.…”

Section: Introductionmentioning

confidence: 99%

Surface morphology of tungsten exposed to helium plasma at temperatures below fuzz formation threshold 1073 K

et al. 2016

View full text Add to dashboard Cite

An impact of crystal orientation on the surface morphology of the helium plasma exposed tungsten has been investigated on the linear device PSI-2.A nanoscale undulating surface structure which has a periodic arrangement is formed for temperatures below 1073 K, in contrast to the fuzz nanostructure formation in a higher temperature range. The crests of undulation align with the <100> direction.The interval of the undulation is the narrowest at the crystal grain of {110} surface.The interval becomes wider as the crystal grain surface is tilting away from the {110} surface, and the undulating surface structure is not formed near the {100} surface. The height of undulations is ∼ 8 nm independently of the interval of the undulations, and it corresponds to a depth of the layer heavily damaged sue to helium plasma exposure.

show abstract

Section: Introductionmentioning

confidence: 99%

Surface morphology of tungsten exposed to helium plasma at temperatures below fuzz formation threshold 1073 K

et al. 2016

View full text Add to dashboard Cite

show abstract

“…The shell shall be manufactured by hot forming/bending and welding. Given the single-shell design, a proper heat shield, similar to the one already provided for Wendelstein 7-X [4], will be subject of future studies. The heat shield will be designed in order that the VV achieves a reference temperature of 100 • C.…”

Section: The Vacuum Vessel and The First Wallmentioning

confidence: 99%

The DTT device: First wall, vessel and cryostat structures

Gironimo

Marzullo

Mozzillo

et al. 2017

Fusion Engineering and Design

View full text Add to dashboard Cite

“…Two types of carbon tiled water cooled heat shields 8 are developed, covering about 40 % of the W7-X wall, which can sustain average loads up to 150 kW/m 2 (respectively 350 kW/m 2 ) and locally up to 250 (500) kW/m 2 . Additional diagnostic heat shields using the same technology have been specially designed to protect in-vessel diagnostics components like the diamagnetic loop and the Soft-X-ray multi-c a m e r a t o m o g r a p h y s y s t e m ( X M C T S ) i n t h e triangular shaped plasma plane.…”

Section: A Predominantly Convective Loadsmentioning

confidence: 99%